Influence of High Temperature Oxidation on Hydrogen Absorption and Degradation of Zircaloy-2 and Zr 700 Alloys - Publication - Bridge of Knowledge

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Influence of High Temperature Oxidation on Hydrogen Absorption and Degradation of Zircaloy-2 and Zr 700 Alloys

Abstract

The present research was aimed at determining the effects of the oxide layers on hydrogen absorption, microstructure and mechanical properties of the Zircaloy- 2 and Zr 702 alloys. The oxidation was made at 350 °C, 700 °C and 900 °C for 10 to 30 min in laboratory air, followed by hydrogen cathodic charging for 72 h and annealing at 400 °C for 4 h. The slow strain rate tests were carried out on oxidized, charged and annealed specimens. The oxidation resulted in thick and cracked, more for Zr 702 alloy, layer. After oxidation at 350 °C, the appearance of hydrides in Zircaloy-2 and absence of hydrides in Zr 702 alloy were observed. After oxidation at high temperatures no current flow was noticed at applied voltage up to 5 V, and no hydrogen or hydrogen cracks. The observed effects were attributed to the phase structure of investigated alloys at low hydrogen content.

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Category:
Articles
Type:
artykuł w czasopiśmie wyróżnionym w JCR
Published in:
HIGH TEMPERATURE MATERIALS AND PROCESSES no. 38, pages 8 - 15,
ISSN: 0334-6455
Language:
English
Publication year:
2019
Bibliographic description:
Zieliński A., Cymann A., Gumiński A., Hernik A., Gajowiec G.: Influence of High Temperature Oxidation on Hydrogen Absorption and Degradation of Zircaloy-2 and Zr 700 Alloys// HIGH TEMPERATURE MATERIALS AND PROCESSES. -Vol. 38, (2019), s.8-15
DOI:
Digital Object Identifier (open in new tab) 10.1515/htmp-2017-0074
Bibliography: test
  1. A. Zielinski and S. Sobieszczyk, Intl. J. Hydrogen Energy, 36 (2011) 8619-8629. open in new tab
  2. T.R. Allen, R.J.M. Konings and A.T. Motta, Corrosion of Zirconium Alloys, [in] Comprehensive Nuclear Materials edited by R.J.M. Konings, Elsevier, Amsterdam, Vol. 5 (2012), pp. 49-68. open in new tab
  3. C. Yan, R. Wang, Y. Wang, X. Wang and G. Bai, Nucl. Eng. Techn., 47 (2015) 323-331. open in new tab
  4. M. Nader and A. Mohamed, Nucl. Sci. Eng., 173 (2013) 172-181.
  5. U. Kamachi Mudali, A. Ravi Shankar, R. Natarajan, N. Saibaba and B. Raj, Nucl. Techn., 182 (2013) 349-357. open in new tab
  6. J. Jayaraj, K. Thyagarajan, C. Mallika and U. Kamachi Mudali, Nucl. Techn., 191 (2015) 58-70. open in new tab
  7. M. Steinbrück and M. Böttcher, J. Nucl. Mater., 414 (2011) 276- 285. open in new tab
  8. N. Selmi and A. Sari, Adv. Mater. Phys. Chem., 3 (2013) 168- 173. open in new tab
  9. C. Zeng, Y. Ling, Y. Bai, R. Zhang, X. Dai and Y. Chen, Intl. J. Hydrogen Energy, 41 (2016) 7676-7690. open in new tab
  10. J.H. Baek and Y.H. Jeong, J. Nucl. Mater., 372 (2008) 152-159. open in new tab
  11. J. Birchley and L. Fernandez-Moguel, Ann. Nucl. Energy, 40 (2012) 163-170. open in new tab
  12. L. Lanzani and M. Ruch, J. Nucl. Mater., 324 (2004) 165-176. open in new tab
  13. M. Le Saux, J. Besson, S. Carassou, C. Poussard and X. Averty, Eng. Fail. Analys., 17 (2010) 683-700.
  14. S. Yamanaka, D. Setoyama, H. Muta, M. Uno, M. Kuroda, K. Takeda and T. Matsuda, J. Alloys Comp., 372 (2004) 129-135. open in new tab
  15. G. Bertolino, G. Meyer and J. Perez Ipiña, J. Alloys Comp., 330- 332 (2002) 408-413. open in new tab
  16. G. Bertolino, G. Meyer and J. Perez Ipiña, J. Nucl. Mater., 320 (2003) 272-279. open in new tab
  17. M.S. Blackmur, J.D. Robson, M. Preuss, O. Zanellato, R.J. Cernik, S.-O. Shi, F. Ribeiro and J. Andrieux, J. Nucl. Mater., 464 (2015) 160-169. open in new tab
  18. S.I. Hong, K.W. Lee and K.T. Kim, J. Nucl. Mater., 303 (2002) 169-176. open in new tab
  19. J.H. Kim, M.H. Lee, B.K. Choi and Y.H. Jeong, J. .
  20. Alloys Comp., 431 (2007) 155-161. open in new tab
  21. K.W. Lee and S.I. Hong, J. Alloys Comp., 346 (2002) 302-307. open in new tab
  22. S.-J. Min, M.-S. Kim and K.-T. Kim, J. Nucl. Mater., 441 (2013) 306-314. open in new tab
  23. J.-H. Huang and M.-S. Yeh, Met. Mater. Trans. A, 29 (1998) 1047-1056. open in new tab
  24. S. Oh, C. Jang, J.H. Kim and Y.H. Jeong, Mater. Sci. Eng., 527 (2010) 1306-1313. open in new tab
  25. W. Chen, L. Wang and L. Shigang, J. Alloys Compd., 469 (2009) 142-145. open in new tab
  26. P.A. Schweitzer, Fundamentals of Metallic Corrosion: Atmospheric and Media Corrosion of Metals, Chpt. 22: Zirconium, CRC Press (2006), pp. 581-582. open in new tab
  27. K.M. McHugh, J.E. Garnier, S. Rashkeev, M.V. Glazoff, G.W. Griffith and S.M. Bragg-Sitton, High Temperature Steam Corrosion of Cladding for Nuclear Applications: Experimental, [in] Ceramic Materials for Energy Applications III, edited by Hua-Tay Lin, Yutai Katoh, Alberto Vomiero, Soshu Kirihara, Sujanto Widjaja, The Amer. Ceram. Soc Wiley Online Library., (2014), pp. 149-160. open in new tab
  28. G. Sundell, M. Thuvander and H.-O. Andren, Corr. Sci., 102 (2016) 490-502. open in new tab
  29. M.B. Elmoselhi, J. Alloys Compd., 231 (1995) 716-721. open in new tab
  30. A. Couet, A.T. Motta and R.J. Comstock, J. Nucl. Mater., 451 (2014) 1-13. open in new tab
  31. M. Große, E. Lehmann, M. Steinbrück, G. Kühne and J. Stuckert, J. Nucl. Mater., 385 (2009) 339-345. open in new tab
  32. J. Blach and L. Falat, High Temp. Mater. Proc., 33 (2014) 329-337. open in new tab
  33. P. Chakraborty, A. Moitra and T. Saha-Dasgupta, J. Nucl. Mater., 466 (2015) 172-178. open in new tab
  34. A. Zieliński et al.: Oxidation and Hydrogen Degradation of Zr Alloys open in new tab
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